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  • (-) PSI Authors = Ferroukhi, Hakim
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Treatment of the implicit effect in Shark-X
Hursin, M., Pelloni, S., Vasiliev, A., & Ferroukhi, H. (2020). Treatment of the implicit effect in Shark-X. Annals of Nuclear Energy, 138, 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
Screening analysis for pressurized thermal shock (PTS) transient scenarios
Mukin, R., Clifford, I., Costa Garrido, O., Mora, D. F., Niffenegger, M., Niceno, B., & Ferroukhi, H. (2019). Screening analysis for pressurized thermal shock (PTS) transient scenarios. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 2536-2549). American Nuclear Society (ANS).
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2019). Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 2209-2222). American Nuclear Society (ANS).
Correlation <em>ν̅</em> <sub><em>p</em><em> </em></sub>– <em>σ </em>for U-Pu in the thermal and resonance neutron range via integral information
Rochman, D., Vasiliev, A., Ferroukhi, H., Pelloni, S., Bauge, E., & Koning, A. (2019). Correlation ν̅ p σ for U-Pu in the thermal and resonance neutron range via integral information. European Physical Journal Plus, 134, 453 (12 pp.). https://doi.org/10.1140/epjp/i2019-12875-7
On the characteristics of the flow and heat transfer in the core bypass region of a PWR
Clifford, I., Pecchia, M., Puragliesi, R., Vasiliev, A., & Ferroukhi, H. (2018). On the characteristics of the flow and heat transfer in the core bypass region of a PWR. Nuclear Engineering and Design, 330, 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039
Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2018). Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study. In Vol. 8. Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance (pp. ICONE26-81743 (13 pp.). https://doi.org/10.1115/ICONE26-81743
Monte Carlo nuclear data adjustment via integral information
Rochman, D., Bauge, E., Vasiliev, A., Ferroukhi, H., Pelloni, S., Koning, A. J., & Sublet, J. C. (2018). Monte Carlo nuclear data adjustment via integral information. European Physical Journal Plus, 133(12), 537. https://doi.org/10.1140/epjp/i2018-12361-x